ML17052A331
| ML17052A331 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/24/2017 |
| From: | Bruce Watson Reactor Decommissioning Branch |
| To: | Hobbs T Crystal River, FL |
| VAALER M, 415-3178, T08F05 | |
| References | |
| GL-16-001 | |
| Download: ML17052A331 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 24, 2017 Mr. Terry D. Hobbs General Manager, Decommissioning Crystal River Nuclear Plant (NA2C) 15760 W. Power Line Street Crystal River, FL 34428-6708
SUBJECT:
CLOSEOUT OF GENERIC LETTER 2016-01, MONITORING OF NEUTRON-ABSORBING MATERIALS IN SPENT FUEL POOLS On April 7, 2016, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16097A169), to address the degradation of neutron-absorbing materials in wet storage systems for reactor fuel at power and non-power reactors.
GL 2016-01 requested licensees provide information to allow the NRC staff to verify continued compliance through effective monitoring to identify and mitigate any degradation or deformation of neutron-absorbing materials credited for criticality control in spent fuel pools.
To facilitate each licensees response, GL 2016-01 established four categories (Category 1, Category 2, Category 3, and Category 4). The categories were established to identify situations where a detailed response to GL 2016-01 would not be required. The categorization criteria were generally based on whether a licensee credits neutron-absorbing materials for criticality control, or if a licensee has, or will soon have, an approved monitoring program for neutron-absorbing materials in the plant technical specifications or as a license condition. A full description of the categories can be found in the enclosure to this letter.
Duke Energy Florida, LLC submitted a response to GL 2016-01 for the Crystal River Unit 3 Nuclear Generating Plant (CR-3) on October 19, 2016 (ADAMS Accession No. ML16293A883).
The NRC staff has completed its review of this response. The NRC staff performed a thorough review of the licensees response, any documents referenced therein, and other applicable licensing basis documents. In the response, the licensee stated that CR-3 belongs in Category 3 based on previous evaluations by the NRC staff. The NRC staff does not agree with this interpretation of the Category 3 criteria, because no monitoring program was explicitly incorporated as a technical specification change or a license condition. However, the NRC staff reviewed the information previously submitted to the NRC, as referenced in Duke Energys October 19, 2016, response, and determined that the information provided was sufficient to meet the intent of responding to GL 2016-01.
In particular, the NRC approved an evaluation by the licensee demonstrating that the neutron-absorbing material in the CR-3 spent fuel pool will continue to perform its safety function through the end of 2019. In order to ensure that the neutron-absorbing materials are not credited for criticality control beyond this time without further evaluation, the licensee
incorporated a statement in their Updated Final Safety Analysis Report that explicitly states that if fuel continues to be stored in the CR-3 spent fuel pool beyond December 31, 2019, the licensee must submit a license amendment request to incorporate monitoring programs for the neutron-absorbing materials in their technical specifications. This ensures that the licensee cannot change their licensing basis with respect to neutron-absorbing materials without NRC review and approval.
Based upon the information submitted by the licensee in response to GL 2016-01, the NRC staff has determined that the submission appears to address the information requested in GL 2016-01, and no further information or action is requested regarding this matter.
Sincerely,
/RA/
Bruce A. Watson, CHP, Chief Reactor Decommissioning Branch Division of Decommissioning, Uranium Recovery, and Waste Program Office of Nuclear Material Safety and Safeguards Docket No. 50-302
Enclosure:
List of GL 2016-01 Categories cc: Distribution via Listserv
- via email OFFICE NMSS/DUWP/RDB/PM NMSS/DUWP/RDB/LA NRR/DE/ESGB/BC(A)
NAME JHickman CHolston EWong*
DATE 2/22/17 2/22/17 2/22/2017 OFFICE NRR/DPR/PGCB/BC NRR/DSS/SNPB/BC NMSS/DUWP/RDB/BC NAME SStuchell*
RLukes*
BWatson DATE 2/17/17 2/17/17 2/24/17
Enclosure LIST OF GL 2016-01 CATEGORIES Category 1:
Power reactor addressees that do not credit neutron-absorbing materials other than soluble boron in the analysis of record (AOR). In some cases, no neutron-absorbing material is present in the spent fuel storage racks, and in other cases, credit for the neutron-absorbing material has been removed through a regulatory action (e.g., approved license amendment). Those addressees may submit a response letter confirming that no neutron-absorbing materials are currently credited to meet U.S. Nuclear Regulatory Commission (NRC) subcriticality requirements in the spent fuel pool (SFP).
Category 2:
Power reactor addressees that have an approved license amendment to remove credit for existing neutron-absorbing materials and that intend to complete full implementation no later than 24 months after the issuance of this Generic Letter (GL). Licensees may request extensions to this implementation timeframe if there are extenuating circumstances. Those addressees may submit a response letter affirming that they will implement the approved license amendment request within the specified time. However, they must still provide information equivalent to Category 3 or Category 4 for any other neutron-absorbing material credited in the SFP criticality AOR after the license amendment has been fully implemented.
Category 3:
Power reactor addressees that have incorporated their neutron-absorbing material monitoring programs into their licensing basis through an NRC-approved Technical specification (TS) change or license condition. Those addressees may submit a response letter referencing their approved TS change or license condition and affirming that no change has been made to their neutron-absorbing material monitoring program, as described in the referenced license amendment request. If a change has been made since NRC approval of the reference, the response letter should also describe any such changes. (Licensees with a monitoring program approved as part of a license amendment request or license renewal application that was not incorporated as a TS change or license condition are considered to belong in Category 4.)
Category 4:
All other power reactor addressees. The NRC seeks information in five areas depending upon the type of neutron absorber material used by the licensee in the spent fuel pool.